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Category:Letter
MONTHYEARIR 05000390/20250102024-11-0404 November 2024 Notification of an NRC (FPTI) (NRC Inspection Report 05000390/2025010 0500039/ 2025010) (RFI) IR 05000277/20240032024-11-0404 November 2024 Integrated Inspection Report 05000277/2024003 and 05000278/2024003 CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20243012024-10-17017 October 2024 Operator Licensing Examination Approval 05000390/2024301 and 05000391/2024301 ML24282B0412024-10-15015 October 2024 Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 ML24284A2842024-10-10010 October 2024 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24281A1012024-10-0707 October 2024 Senior Reactor and Reactor Operator Initial License Examinations ML24261C0062024-10-0404 October 2024 Correction to Amendment No. 134 to Facility Operating License No. NPF-90 and Amendment No. 38 to Facility Operating License No. NPF-96 ML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24284A1072024-09-26026 September 2024 Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24221A2582024-09-0606 September 2024 Response to Request for Re-Engagement Regarding the Subsequent License Renewal Environmental Review for Peach Bottom Atomic Power Station, Units 2 and 3 05000277/LER-2024-003, Automatic Reactor Scram Following Main Turbine Trip Due to Degraded Condenser Vacuum2024-09-0505 September 2024 Automatic Reactor Scram Following Main Turbine Trip Due to Degraded Condenser Vacuum 05000390/LER-2024-002, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-09-0505 September 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation IR 05000277/20240052024-08-29029 August 2024 Updated Inspection Plan for Peach Bottom Atomic Power Station, Units 2 and 3 (Report 05000277/2024005 and 05000278/2024005) IR 05000390/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390-2024005 and 05000391-2024005 ML24218A1442024-08-27027 August 2024 Issuance of Amendment Nos. 169 and 75 Regarding Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate ML24235A0342024-08-23023 August 2024 U.S. Nuclear Regulatory Commission’S Analysis of Constellation Energy Generation’S Decommissioning Funding Status Report IR 05000277/20240102024-08-23023 August 2024 Fire Protection Team Inspection Report 05000277/2024010 and 05000278/2024010 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000390/20244022024-08-20020 August 2024 – Security Baseline Inspection Report 05000390-2024402 and 05000391/2024402 - Public CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08), IR 05000482/20240052024-08-14014 August 2024 Updated Inspection Plan for Wolf Creek Generating Station (Report 05000482/2024005) IR 05000277/20240022024-08-14014 August 2024 Integrated Inspection Report 05000277/2024002 and 05000278/2024002 ML24225A1692024-08-12012 August 2024 10 CFR 50.46 Annual Report ML24219A0262024-08-12012 August 2024 Request for Withholding Information from Public Disclosure ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000390/20240022024-08-0707 August 2024 Integrated Inspection Report 05000390/2024002 and 05000391/2024002 Rev ML24214A3232024-08-0101 August 2024 Response to Request for Additional Information - Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification ML24204A2652024-07-25025 July 2024 Regulatory Audit Summary Related to Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate ML24206A1252024-07-24024 July 2024 Revision of Three Procedures and Two Forms That Implement the Radiological Emergency Response Plan (RERP) ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24170A8002024-07-15015 July 2024 Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter IR 05000390/20244402024-07-12012 July 2024 95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter 05000391/LER-2024-003, Inoperability of Both Trains of Unit 2 Low Head Safety Injection2024-07-11011 July 2024 Inoperability of Both Trains of Unit 2 Low Head Safety Injection ML24191A0612024-07-0606 July 2024 Independent Spent Fuel Storage Installation (ISFSI) - Annual Radioactive Effluent Release Report ML24131A0012024-07-0202 July 2024 Issuance of Amendment Nos. 167 and 73 Regarding Adoption of Technical Specification Task Force Traveler TSTF-427-A, Revision 2 CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024 Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) ML24178A4142024-06-26026 June 2024 Revision of One Procedure and One Form That Implement the Radiological Emergency Response Plan (RERP) ML24178A3672024-06-26026 June 2024 Correction to 2023 Annual Radioactive Effluent Release Report – Report 47 CNL-24-018, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS2024-06-25025 June 2024 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS 2024-09-06
[Table view] Category:Part 21 Correspondence
MONTHYEARML19008A0432019-01-0404 January 2019 Third Interim Notification Per 10 CFR Part 21 Degraded Snubber SF1154 Hydraulic Fluid Batch No. 11KLVS146 ML17179A3782017-06-0707 June 2017 TE Connectivity - Part 21 Transfer of Information TE-023 ML15105A3462015-03-23023 March 2015 NSAL-15-2 - Impact of a Break in the Reactor Coolant Pump No. 1 Seal Leak-off Line Piping on Seal Leakage During a Loss of Seal Cooling Event ML15022A6502015-01-20020 January 2015 Letter from Steven R. Eisenberg USNRC 10CFR Part 21 Notification ML14079A0272014-03-13013 March 2014 Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve ML13246A0872013-08-23023 August 2013 Nuclear Nonconformance Event Number 49302 - 10CFR21 Notification ML13044A0752013-02-0808 February 2013 Part 21 - Completed Evaluation for Potential Error in Main Steam Line High Flow Calculational Methodology ML12326A7142012-11-21021 November 2012 Fourth Interim Report Pursuant to 10 CFR 21 - Unexpected Degradation of Vital Batteries Lll and Lv ML12206A0552012-07-24024 July 2012 Second Interim Report Pursuant to 10 CFR 21 - Unexpected Degradation of Vital Batteries III and IV ML1024605372010-09-0202 September 2010 Part 21 60-Day Interim Report Notification: Failure to Include Seismic Input in Channel-Control Blade Interference Customer Guidance ML0828003372008-10-0303 October 2008 Namco, Transmittal of 10CFR Part 21 Report - Thread Sealant Issue ML0714302622007-05-17017 May 2007 10 CFR Part 21 Report Concerning 3 and 4 Borg Warner Check Valves, Amendment of Information Previously Supplied ML0529103892005-10-13013 October 2005 Part 21 Communication: Testing to ANSI Standards Complete on Circuit Breaker Replacement Primary Bushings ML0501102232005-01-0707 January 2005 Non-Emergency Event Report, Overstress Condition on Single Failure Proof Crane Trolleys ML0428002672004-09-29029 September 2004 Submittal of Part 21 Final Report: Non-conservative SLMCPR ML0335301272003-12-16016 December 2003 Part 21 Report on Potential Concern Regarding Specific Lot of Fluorocarbon Rubber Inserts ML0320604292003-07-21021 July 2003 Notification of Possible Defect Associated with Thermo Westronics Model 2100C Series Recorders 2019-01-04
[Table view] |
Text
t GE Energy Jason. S. Post Manager, Engineering Quality & Safety Evaluations 3901 Castle Hoyne Rd..
Wilmington, NC 28401 USA T 910 675-6608 F910 362 6608 Jason.postdge.com October 13, 2005 MFN 05-107 Attn: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Part 21 Communication: Testing to ANSI Standards Complete on Circuit Breaker Replacement Primary Bushings
Reference:
MFN 05-065, Part 21 Communication: Circuit Breaker Replacement Primary Bushings Not Tested to ANSI Standards, July 14, 2005 The reference letter provided information concerning failure to perform required ANSI C37 Industry Standards for Switchgear testing for replacement primary bushings used in Magne-Blast circuit breakers. The replacement primary bushings were provided by GE Supply PSC, Sharon Hills, PA, and supplied to 2 licensees by GE Energy - Nuclear (GE) as safety related components. The discrepancy has been eliminated by the responsible GE product department through successful completion of the required ANSI testing.
Summary As reported inthe reference letter, GE determined that design tests inaccordance with certain ANSI C37 Industry Standards for Switchgear were not performed prior to implementation of bushing design changes for Parts Q0845D0123G001, and Q0845D0124G001 and G003, which have been delivered to Peach Bottom 2,3 and Watts Bar 1 for use as replacement primary bushings in Magne-Blast circuit breakers. The design changes were to the insulation material used in the primary bushing, and in the primary bushing fabrication process. When the design changes were made, they were judged to be acceptable based on similarity to the existing designs plus mechanical testing. However, GE discovered that the required testing in accordance with ANSI C37 was not performed when the design changes were made.
Inresponse to this discovery, testing to the applicable ANSI standard was initiated, with a commitment to complete the testing and report the results by October 18, 2005. The testing to ANSI C37 has been complete and it has been determined that the subject bushings meet the applicable standards.
General Electric Company
- MFN 05-107 Page 2of2 Safety Basis The primary bushings identified above for use in nuclear safety related applications have been confirmed to meet applicable ANSI standards.
Corrective/Preventive Actions No actions are needed as a result of this communication.
Recommendations Any of these primary bushings being held in inventory pending successful completion of the ANSI standards testing may now be released from inventory as needed.
If you have any questions, please call me at (910) 675-6608.
Sincerely, Jason. S. Post, Manager Engineering Quality & Safety Evaluations cc: S. B.Alexander (NRC-NRR/DISP/PSIM) Mail Stop 6 F2 M. B. Fields (NRC-NRR/DLPM/LPD4) Mail Stop 7 El C.V. Hodge (NRC-NRR/DIPM/IROB) Mail Stop 12 H2 M. E. Harding (GE)
J. F.Harrison (GE)
J. F.Klapproth (GE)
L. M. Quintana (GE)
G.B. Stramback (GE)
G.A. Watford (GE)
PRC File
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Jason Post GE Energy ,XFPO~t,,
P.O. Box 780, M/C L-10 Wilmington, NC 28401 02 1A $ 00.370 0004319382 COT 14 '2005 MAILED FROM ZIPCODE 28402 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop 0-3H8 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 1,1,II11 1,,1,,1.,1,1,,,1,1,, II1,1,,1,1,.1,,1..1,1,.